Abstract
This paper describes the conceptual design and analysis of the vacuum chamber for the Compact Ignition Tokamak (CIT). The chamber consists of the first wall (FW), divertor, and vacuum vessel (VV) assemblies. The FW and divertor are constructed of inertially cooled graphite tiles which entirely cover the VV. The latter is a continuous, resistive shell of Inconel 625 cooled with gaseous nitrogen. Thermal and stress analysis of FW and divertor have established a nominal tile thickness of 1.0 cm and a maximum allowable FW surface heat flux of 11.0 MW/m2. Calculations have shown that for a cooldown time of one hour, the required tile-to-VV thermal conductance is >0.1 W/K. Estimates of worst-case electromagnetic loads and resulting stresses on the VV during plasma disruptions have shown the maximum stress levels to be below the allowable limits for the VV material.
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